Din avgränsning ger 189 träffar.
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2012:62 Technical Note, Review of the MARFA Code
As part of SSM’s Initial Review Phase of SKB’s SR-Site safety assessment of the final disposal of spent nuclear fuel at the Forsmark site, Quintessa has been requested by SSM to review SKB’s MARFA code ... use in SR-Site. This Technical Note summarises the findings of Quintessa’s review. The main concern raised in the review is the poor quality of the documentation associated with the MARFA code, in particular...
Innehållstyp: Publikationer -
2014:50 Technical Note, A Study of Availability of Fuel Data for Sweden’s Spent Nuclear Fuel
The study covers all types spent fuel ... planned to be placed in the final repository. It was carried out by selecting a sample of spent fuel and investigating the information available at the Nuclear Power Plants (NPP’s) in Sweden, the Central...
Innehållstyp: Publikationer -
2016:05 Technical Note, Assessment of SKB TR-14-15 Assessment of SKB TR-14-15 “Possible influence from stray currents from high voltage DC power transmission on copper canisters”
The general objective of the present project is to provide independent review comments for one area of SKB:s post closure safety analysis, SR-Site. With this in mind, the purpose of this report is to review ... SKB’s presentation on possible influence from stray currents from high voltage DC power transmission on a repository for nuclear fuel. Laust B Pedersen SSM English...
Innehållstyp: Publikationer -
2018:04 Systemövergripande frågor
regeringens prövning Slutförvaring av använt kärnbränsle Svensk Kärnbränslehantering AB (SKB) har lämnat in två ansökningar enligt lagen (1984:3) om kärnteknisk verksamhet (kärntekniklagen) om att dels få uppföra ... slutförvarsanläggningen, den långsiktiga strålsäkerheten efter förslutning av slutförvaret respektive systemövergripande frågor. Tillsammans med granskningsrapporterna överlämnar SSM till regeringen en samman-ställning...
Innehållstyp: Publikationer -
2014:29 Technical Note, Independent Modelling of Radionuclide Transport, Evaluation of Colloid Transport Modelling – Main Review Phase
SKB excludes consideration of colloids originating inside the canister in its performance assessment on the basis of the filtration capability of the buffer material. In the canister failure by corrosion ... filtration argument is not entirely valid for excluding modelling in-canister colloids. In this Technical Note, we evaluate the relevance of colloids to dose estimates, including the eroded buffer case. ...
Innehållstyp: Publikationer -
2012:49 Hydrogeological characteristics of sites for low- and intermediate-level waste disposal
Forsmark area with its selected two sites and the Laxemar-Simpevarp area with its two sites are broadly similar in terms of lithology, rock ages, and tectonic histories. The two areas differ in terms of degree ... degree of deformation, and tectonic fabric. Some lithologic and tectonic differences are noticeable between the two sites in the Forsmark area and between the two sites in the Laxemar-Simpevarp area. These...
Innehållstyp: Publikationer -
2012:31 Decommissioning of the Nuclear Reactors R2 and R2-0 at Studsvik, Sweden – General Data as called for under Article 37 of the Euratom Treaty
describes the plans for decommissioning of the nuclear research and material test reactors R2 and R2-0, situated at the Studsvik site in Sweden. The purpose of the document is to serve as information for ... Commission, and to fulfil the requirements of Article 37 of the Euratom Treaty. According to Article 37, each Member State shall provide the Commission with such general data as will make it possible to...
Innehållstyp: Publikationer -
2013:16 Technical Note, Assessment of PWR fuel depletion and of neutron multiplication factors for intact PWR fuel copper canisters – main review phase
Kärnbränslehantering AB) in 2011 applied to the Swedish government for approval of a proposed solution for disposal of used fuel from Swedish nuclear power reactors and some relatively minor quantities of other fissile ... Note contains results of a recent review of the SKB methods used to determine the influence of reactor depletion on keff of intact PWR fuel in an intact PWR copper canister flooded with water. The review has...
Innehållstyp: Publikationer -
2012:60 Technical Note, Handling of climate related issues in the safety assessment SR-Site
based on research carried out over several decades and is an impressive compilation of data and knowledge of the site of Forsmark. The sections on climate, glaciations and permafrost have developed continuously ... some remarks on the way the process is described in the proposal. It is unclear how new research findings can enter and influence the decision process. In addition the background data is difficult to find...
Innehållstyp: Publikationer -
2014:47 Technical Note, Assessment of groundwater salinity evolution at repository depth and especially the impact of dilute water infiltration
entering deposition holes in the repository will be progressively diluted over time because of expected changes of topographic and climatic conditions at Forsmark. This is a long-term safety issue because ... advective movement of sulphide-containing water to the canister surface. SKB’s position in SR-Site is that the hydrogeological properties of the sparsely-fractured bedrock and the processes of water-rock reaction...
Innehållstyp: Publikationer